Physics drivers for the plasma-facing component design of the COMPASS-U tokamak
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F25%3A00648062" target="_blank" >RIV/61389021:_____/25:00648062 - isvavai.cz</a>
Result on the web
<a href="https://iopscience.iop.org/article/10.1088/1361-6587/addc98" target="_blank" >https://iopscience.iop.org/article/10.1088/1361-6587/addc98</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1088/1361-6587/addc98" target="_blank" >10.1088/1361-6587/addc98</a>
Alternative languages
Result language
angličtina
Original language name
Physics drivers for the plasma-facing component design of the COMPASS-U tokamak
Original language description
The main drivers for the metallic plasma-facing component (PFC) design of the COMPASS Upgrade (COMPASS-U) tokamak (BT <= 5 T, IP <= 2 MA, Rgeo = 0.9 m, ageo = 0.27 m, tflattop <= 3 s) derived from physics considerations are presented in this paper. Requirements on the plasma-wall gaps are given based on previous experimental observations in other devices. Gaps at the inner/outer midplane are set to minimum values 20 and 40 mm, respectively, to allow all magnetic equilibria in the lower and upper single-null configurations to fit in the PFC outline, to allow an efficient flow in the scrape-off layer towards the divertor and to minimize the impurity flux from the wall. The closed tungsten divertor was designed with a similar shape to ITER's divertor since COMPASS-U has a similar aspect ratio and uses an ITER-like equilibrium for its baseline scenario. Steady-state thermal loads are calculated at the outer strike-point, where they are expected to be the highest, in attached conditions using a 0D energy balance (>= 150 MW m-2) and in detached conditions using BIT1 kinetic calculations (similar to 70 MW m-2). Transient thermal loads range from 1.2 MJ m-2 for ELMs (maximum parallel peak energy fluence at targets) to 0.6-1.2 GW m-2 in similar to 0.5 ms for high-energy vertical displacement events (maximum perpendicular heat flux density). Electromagnetic loads are calculated during disruptions using an in-house parametric model, accounting for current quench (CQ) and halo current contributions and validated by simulations using the CarMa0NL code, which is able to describe the nonlinear evolution of axisymmetric plasmas in the presence of 3D volumetric structures. The CQ rate is expected to be at least delta IP/delta t = 3 MA ms-1, and the halo current magnitude is set to 75% of the pre-disruptive maximum plasma current, according to the ITPA disruption database, yielding Ihalo = 1.5 MA. Maximum total force acts on the bottom divertor baffle with a value of similar to 60 kN and the corresponding total torque is similar to 4 kN m.
Czech name
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Czech description
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Classification
Type
J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database
CEP classification
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OECD FORD branch
10304 - Nuclear physics
Result continuities
Project
Result was created during the realization of more than one project. More information in the Projects tab.
Continuities
I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace
Others
Publication year
2025
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Name of the periodical
Plasma Physics and Controlled Fusion
ISSN
0741-3335
e-ISSN
1361-6587
Volume of the periodical
67
Issue of the periodical within the volume
6
Country of publishing house
US - UNITED STATES
Number of pages
14
Pages from-to
065030
UT code for WoS article
001505480200001
EID of the result in the Scopus database
2-s2.0-105008149574